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Journal Articles

Ultimate Strength of a Thin Wall Tee for Sodium Cooled Fast Reactors Under Seismic Loads

Tomoyoshi Watakabe, Hideki Takahashi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2023, 145(5): 051502.
Paper No: PVT-23-1034
https://doi.org/10.1115/1.4062675
Published Online: June 16, 2023
View Article titled, Ultimate Strength of a Thin Wall Tee for Sodium Cooled Fast Reactors Under Seismic Loads
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Topics: Design, Failure, Failure mechanisms, Fatigue, Pipes, Stress, Thin wall structures, Dynamic response, Tensile strength, Finite element analysis
Journal Articles

Development of In-Service Inspection Rules for Liquid-Metal Cooled Reactors Using the System Based Code Concept

Shigeru Takaya, Tai Asayama, Hiroki Yada, A. Thomas Roberts, Frank J. Schaaf, Jr.
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2020, 142(2): 021204.
Paper No: PVT-19-1071
https://doi.org/10.1115/1.4044344
Published Online: November 27, 2019
View Article titled, Development of In-Service Inspection Rules for Liquid-Metal Cooled Reactors Using the System Based Code Concept
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Topics: In-service inspection, Liquid metals, Sodium, Pipes, Heat, Breeder reactors, Fracture (Materials), Welded joints, Reliability, Engineering prototypes
Journal Articles

Design and Integrity Evaluation of a Finned-Tube Sodium-to-Air Heat Exchanger in a Sodium Test Facility

Hyeong-Yeon Lee, Hyungmo Kim, Jong-Bum Kim, Ji-Young Jeong
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2017, 139(3): 031203.
Paper No: PVT-16-1097
https://doi.org/10.1115/1.4035038
Published Online: November 4, 2016
View Article titled, Design and Integrity Evaluation of a Finned-Tube Sodium-to-Air Heat Exchanger in a Sodium Test Facility
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Topics: Design, Sodium, Creep, Stress, Heat exchangers, Fatigue, Test facilities
Journal Articles

Ultimate Strength of a Thin Wall Elbow for Sodium Cooled Fast Reactors Under Seismic Loads

Tomoyoshi Watakabe, Kazuyuki Tsukimori, Seiji Kitamura, Masaki Morishita
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2016, 138(2): 021801.
Paper No: PVT-15-1054
https://doi.org/10.1115/1.4031721
Published Online: November 19, 2015
View Article titled, Ultimate Strength of a Thin Wall Elbow for Sodium Cooled Fast Reactors Under Seismic Loads
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Topics: Design, Failure, Failure mechanisms, Fatigue, Pipes, Stress, Tensile strength, Thin wall structures, Fast neutron reactors, Sodium
Journal Articles

Effect of Temperature and Chloride Content on the Stress Corrosion Cracking Susceptibility of 304 Stainless Steel Welded Joints Treated by Ultrasonic Impact Treatment

Gang Ma, Xiang Ling
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2013, 135(5): 051501.
Paper No: PVT-11-1014
https://doi.org/10.1115/1.4005871
Published Online: August 26, 2013
View Article titled, Effect of Temperature and Chloride Content on the Stress Corrosion Cracking Susceptibility of 304 Stainless Steel Welded Joints Treated by Ultrasonic Impact Treatment
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Topics: Corrosion, Stainless steel, Stress corrosion cracking, Surface roughness, Temperature, Testing, Welded joints, Stress, Sodium
Journal Articles

High Temperature Design and Damage Evaluation of MOD.9Cr-1Mo Steel Heat Exchanger

Hyeong-Yeon Lee, Jong-Bum Kim, Hong-Yune Park
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Codes And Standards
J. Pressure Vessel Technol. October 2012, 134(5): 051101.
https://doi.org/10.1115/1.4005938
Published Online: September 10, 2012
View Article titled, High Temperature Design and Damage Evaluation of MOD.9Cr-1Mo Steel Heat Exchanger
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Topics: Creep, Damage, Design, Fatigue, Finite element analysis, Heat exchangers, High temperature, Sodium, Steel, Stress
Journal Articles

Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

N. Mani, G. Thanigaiyarasu, P. Chellapandi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2012, 134(2): 021211.
https://doi.org/10.1115/1.4005385
Published Online: January 25, 2012
View Article titled, Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor
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Topics: Boilers, Finite element methods, Fracture (Materials), Junctions, Leakage, Leak-before-break, Nozzles, Shells, Sodium, Sodium fast reactors
Journal Articles

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

Tai Asayama, Yasuhiro Abe, Noriko Miyaji, Mamoru Koi, Tomohiro Furukawa, Eiichi Yoshida
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. February 2001, 123(1): 49–57.
https://doi.org/10.1115/1.1338119
Published Online: October 27, 2000
View Article titled, Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors
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Topics: Corrosion, Creep, Design, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Sodium, Steel, Fluence (Radiation measurement), Breeder reactors
Journal Articles

Numerical Analysis of Nonstationary Thermal Response Characteristics for a Fluid-Structure Interaction System

T. Muramatsu
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 1999, 121(3): 276–282.
https://doi.org/10.1115/1.2883703
Published Online: August 1, 1999
View Article titled, Numerical Analysis of Nonstationary Thermal Response Characteristics for a Fluid-Structure Interaction System
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Topics: Fluid structure interaction, Numerical analysis, Fluctuations (Physics), Sodium, Temperature, Damping, Liquid metal fast breeder reactors, Simulation, Turbulence, Boundary element methods
Journal Articles

Seismic Vibration Analysis of Fluid-Structure Interaction in LMFBR Piping Systems

F. Hara
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1988, 110(2): 177–181.
https://doi.org/10.1115/1.3265583
Published Online: May 1, 1988
View Article titled, Seismic Vibration Analysis of Fluid-Structure Interaction in LMFBR Piping Systems
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Topics: Fluid structure interaction, Liquid metal fast breeder reactors, Piping systems, Vibration analysis, Pipes, Pressure, Vibration, Waves, Excitation, Sodium
Journal Articles

The Plastic Ratcheting of Thin Cylindrical Shells Subjected to Axisymmetric Thermal and Mechanical Loading

S. Karadeniz, A. R. S. Ponter, K. F. Carter
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1987, 109(4): 387–393.
https://doi.org/10.1115/1.3264921
Published Online: November 1, 1987
View Article titled, The Plastic Ratcheting of Thin Cylindrical Shells Subjected to Axisymmetric Thermal and Mechanical Loading
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Topics: Pipes, Design, Fast neutron reactors, Finite element analysis, Materials properties, Sodium, Stress, Temperature
Journal Articles

The PVRC International Benchmark Project on Simplified Methods for Elevated Temperature Design and Analysis—An Update

D. H. Pai
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1983, 105(1): 85–90.
https://doi.org/10.1115/1.3264246
Published Online: February 1, 1983
View Article titled, The PVRC International Benchmark Project on Simplified Methods for Elevated Temperature Design and Analysis—An Update
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Topics: Design, Temperature, High temperature, Inelastic analysis, Pressure vessels, Sodium, Structural analysis, Structural mechanics
Journal Articles

TRANS2A: An Unconditionally Stable Code for Thermal Transient Stress Analysis in Piping

B. R. Strong, Jr., G. C. Slagis
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1981, 103(1): 50–58.
https://doi.org/10.1115/1.3263370
Published Online: February 1, 1981
View Article titled, TRANS2A: An Unconditionally Stable Code for Thermal Transient Stress Analysis in Piping
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Topics: Pipes, Stress analysis (Engineering), Transients (Dynamics), Stress, Thermal stresses, Heat transfer, Temperature, Temperature gradient, Unsteady flow, Approximation
Journal Articles

Pressure Transient Analysis of Elbow-Pipe Experiments Using the PTA-2 Computer Code

C. K. Youngdahl, C. A. Kot, R. A. Valentin
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1981, 103(1): 33–42.
https://doi.org/10.1115/1.3263368
Published Online: February 1, 1981
View Article titled, Pressure Transient Analysis of Elbow-Pipe Experiments Using the PTA-2 Computer Code
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Topics: Computers, Pipes, Pressure, Transient analysis, Cavitation, Boilers, Breeder reactors, Computation, Deformation, Heat
Journal Articles

Pressure Transient Analysis in Piping Systems Including the Effects of Plastic Deformation and Cavitation

C. K. Youngdahl, C. A. Kot, R. A. Valentin
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1980, 102(1): 49–55.
https://doi.org/10.1115/1.3263301
Published Online: February 1, 1980
View Article titled, Pressure Transient Analysis in Piping Systems Including the Effects of Plastic Deformation and Cavitation
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Topics: Cavitation, Deformation, Piping systems, Pressure, Transient analysis, Pipes, Sodium, Transients (Dynamics), Waves, Boilers
Journal Articles

Mechanical Properties of Roll Extruded Nuclear Reactor Piping

J. M. Steichen, R. L. Knecht
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1976, 98(2): 105–110.
https://doi.org/10.1115/1.3454346
Published Online: May 1, 1976
View Article titled, Mechanical Properties of Roll Extruded Nuclear Reactor Piping
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Topics: Mechanical properties, Nuclear reactors, Pipes, Temperature, Ductility, Sodium, Tensile strength, ASME Standards, Coolants, Crack propagation